IR 05000328/1981018
| ML19350D957 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/12/1981 |
| From: | Coley J, Economos N, Herdt A, York J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19350D956 | List: |
| References | |
| 50-328-81-18, NUDOCS 8105270351 | |
| Download: ML19350D957 (10) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 11
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o 101 MARIETTA ST., N.W.. sulTE 3100 C3 j'
ATLANTA, GEORGIA 30303
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Report No. 50-328/81-18 Licensee:
Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, TN 37401 Facility Name: Sequoyah Docket No. 50-328 License No. CPP9-73 Inspection at Sequoyah site near Chattanooga, TN Inspectors:
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N. Economos Dat v51gned
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J. Cole
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Date Signed
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J. Yor Date Sigrred Approved by:
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N A. R. Herdt,;
. ion Chief Da'te Signed Engineering Inspection Branch Engineering and Technical Inspection Division
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SUMMARY Inspected on April 13-16, 1981 Areas Inspected This routine, unannounced inspection involved 78 inspector-hours onsite in the l
areas of safety related pipe supports and restraints; record review of preservice inspection activities and safety related structures / supports outside containment; licensee identified items; inspector identified items.
Results Of the five areas inspected, no violations or deviations were icentified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees G. G. Stack, Project Manager
"T. B. Northern, Jr., Construction Engineer
- D. W. Mack, Assistant Construction Engineer
- 0. W. Kelley, Supervisor, Construction Quality Control Record Unit
- H. Gelston, Electrical Engineer Compliance Power
"K. G. Galloway, Supervisor, Mechanical and Welding W. M. Halley, Preoperation Test Supervisor R. Simmons, Mechanical Engineer Valve Coordinator M. Eisenbise, Mechanical Engineer, Outage Section N. Thomas, Preoperational Test Engineer, Ventilation S. B. Miller, Assi: cant Construction Engineer, Quality Control Records Other licensee employees contacted included construction craftsmen and technicians.
" Attended exit interview
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2.
Exit Interview The inspection scope and findings were summarized on April 16, 1981 with those persons indicated in paragraph 1 above. The inspectors expressed concern over the apparent lack of communications and coordination existing between the licensees licensing staff and site personnel in following the progress of open items.
This was demonstrated by the fact that out' of a list of approximately 94 items reported as ready to close, the inspectors preselected 19 for review.
Upon arrival at the site discussions with cognizant personnel disclosed that only six (6) of these were ready for review.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Violation, 328/80-22-01, Failure of weld to blend smoothly
into adjacent base metal.
A TVA-SNP letter of respoc+e dated January 26, 1981 has been reviewed and determined to be acceptable by Region II. The inspectors held discussions with cognizant unit super-visor and examined the corrective actions as stated in the letter of response.
The inspectors concluded that TVA-SNP had determined the full extent of the subject noncomoliance, performed the necessary survey and fol-low-up actions to correct the present conditions and developed the
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necessary corrective action to preclude recurrences of similar circum-stances. The corrective actions identified in the letter of response have been implemented.
b.
(0 pen) Deficiency No. 328/80-08-03, Failure of records to adequately
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i define practical examination criteria. The inspectors were provided a
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copy of a " Practical Examination". checkoff sheet for a Level I examiner. No check off sheet has been developed for a Level II exam-iner, nor was there evidence provided that described the type of test
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i specimen that the examiner tested for qualification. This item remains open pending completion of licensee's corrective action.
c.
(0 pen) Deficiency 328/80-08-01, Failure to comply with preservice/
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inservice inspection requirements. TVA-SNP letter of response dated May 23, 1980 has been reviewed and determined to be acceptable by Region II, However, the inspectors concluded by observation and interviews that TVA-SNP had not fully achieved the corrective actions stated in the letter of response. This item will remain open until SI-114 his been revised to specify the schedule for Unit 2 inservice inspection, d.
(Closed) Unresolved item 328/80-11-01 Potential inadequate preservice/
inservice inspection program. The licensee has revised the Operational
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Quality Assurance Manual, Part II, Section 5.1 to correct the QA
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functions identified as being inadequately addressed.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Licensee Identified Item 50.55(e)
a.
(Closed) 328/79-28-01 RHR Pump Motor Service Factor NEB 79-03. Flow
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restrictors were added in each RHR pump hot leg and cold leg injection j
header to provide the pressure drop necessary to prevent pump motor overloading. The inspectors reviewed the work package, drawings, weld
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maps, observed the completed welds and reviewed related quality records and radiographs. Work completion was approved on November 15, 1979.
b.
(Closed) 328/81-02-28 Diesel Interlock Design Deficiency SWP-8026. As stated in the licensee's final report dated January 9,1981, interlocks were added to the emergency feeder breaker automatic close circuit.
These interlocks were needed to ensure load shedding prior to allowing the emergency feeder breaker to close. The inspectors reviewed veri-fication by site QA on forms M&AI-;2, Attachment A and records of functional tests completed on December 12, 1980. The latter had been
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approved by the cogni:: ant site engineer. Other documents reviewed
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included nonconformance report SWP8026, engineering change notice
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L5363, unreviewed safety c,uestion determination, form TVA 10551 and related drawings.
c.
(Closed) 328/81-02-16 Nonreinforced Concrete Masonry Block Walls, CEB-8031. Installation of restraints on nonreinforced concru:e masonry walls located in Category I structures was completed on March 30, 1981.
Areas where these walls were located included the charging pump rooms, centrifugal charging pump room, boric acid evaporator room, containment spray pump rooms A and B.
The inspectors observed the restraints and reviewed applicable drawings to ascertain compliance with as-built conditions. Certain engineering aspects on this matter were reviewed on a previous inspection documented in report number 50-328/81-04.
d.
(Closed) 328/81-02-14 ERCW Pump Motor Relays, EEB-8022. As stated in the licensee's revised final report dated January 23, 1981 the over-current relays for the 700-hp ERCW pump motors have been replaced with General Electric type IA66 having a tap range of 2.5 to 5.0 amperes.
The inspectors reviewed related QC forms and observed the newly installed relays.
e.
(Closed) 328/80-09-02 Ruskin Fire Dampers, MEB-8001/8004. The modifi-cation on the Ruskin vertical spring close IBD fire dampers was completed on June 16, 1980. The inspectors discussed the "fix" with the licensee's cognizant engineer and reviewed related QA/QC documents
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including work plan and instruction sheet drawings, functional test reports and the vendor's (Ruskin) certificate of conformance on the work performed.
f.
(Closed) 328/81-02-20 Pressurizer Safety Valve Spring, NCR-2397. As stated in the licensee's final report dated November 26, 1980 the broken spring, in pressurizer safety valve No. 2-RV-68-565, was replaced with one supplied by the vendor, Crosby Live and Gage Company. A metallurgical investigation performed on the failed spring j
attributed the initiation of the failure to a quench crack generated l
during the thermal treatment.
Stresses generated from the quench process and during subsequent tests appear to have contributed to the failure.
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A surface examination (MT) of similar type pressurizer safety valve springs in Unit 2 found them to be satisfactory. The vendor's report asserted that the failure was an isolated case, in that, no other failures have been reported by nuclear and non-nuclear users of the l
valves.
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(Closed) 328/81-02-03 Omitted Pipe Protective Devices, CEB-8009 & 8010.
Work to install one pipe rupture protective device on a two-inch UHI
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line and two other such devices on a steam generator blowdown line was
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completed. This omission was discovered during a review of analysis performed by EDS Nuclear Inc. The inspectors reviewed the l wensee's final report dated May 29, 1980, the work package and related QA/QC records.
Excessive temperatures inside containment precluded the visuas inspection / observation of these devices, h.
(Closed) 328/81-02-10 Deficiencies in Installed Pipe Hangers and Discharge Piping in the ERCW Pumping Station, NRC-2246 & 2259. As stated in the licensee's final report dated September 4, 1980, those hangers determined to be unacceptable were reworked to meet analysis requirements.
Also results of a review performed by TVA's design personnel determined that the location of the discharge piping would not alter the original analysis, and the piping was therefore accept-able in the "as-installed" configuration.
The engineering change notice and work plan were reviewed for clarity, completeness and accuracy. The reviewed documents had been signed by cognizant person-nel assigned to this task.
1.
(Ope'n) 328/79-16-01 Vibration in RHR Piping CEB 79-04 The licensee's final report dated November 15, 1979 stated in part that the reported deficiencies were applicable only to Unit 1.
However as a result of discussions, interviews, observations and record review the inspectors ascertained that corrective action had been implemented in Unit 2 as well. Therefore, the inspectors requested and the licensee agreed to provide a revised final report delineating the action taken in Unit 2.
The inspectors stated that ti.is item will remain open until RII has an opportunity to review the revisii eport.
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f.
(Closed) 328/81-02-13 Analysis of Intermediate Break Location, CEB-8027. As stated in the licensee's final report dated January 21, 1981 a reevaluation of the lines in question, (a) safety inje'ction, cold leg injection loop 4 and (b) resistance temperature device line loop 2 has found no unacceptable interactions. Whereas, in the case of residual heat removal hot leg recirculation line, a reevaluation established that no stresses would result for which new breaks must be postulated, the original break locations were valid. Therefore, no i
protective device modifications were required for any of the three lines.
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(Closed) 328/81-02-09 Incorrect Valve Weights in Auxiliary Feedwater Piping, CEB 8023. As stated in the licensee's final report dated October 22, 1980, the auxiliary feedwater piping system has been
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reanalyzed and the necessary modifications have been performed. The i
inspectors reviswed related work plans, engineering change notice (s),
drawings and observed valve and hangers affected. Work on this item was completed on Maren 17, 1981.
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1.
(Closed) 328/81-18-01 Leakage of Metal Bellows on Primary Containment Penetration, NCR 2519. The licensee's final report dated February 12, 1981 stated that because of undue difficulty in gaining access to the defective weld on the internal bellows of primary containment penetra-
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tion X-30, Azimuth 291*, it was decided to weld a larger diameter bellows concentric with the original.
This reestablished containment pressure integrity and ensured testing ability.
The inspectors reviewed related work plans, drawings, weld maps, field fabrication records and radiographs. Excessive temperatures inside containment and
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inaccessability precluded a visual inspection of the completed welds at this time.
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6.
Independent Inspection Effort Status of IE Bulletin 79-14 Sequcyah Unit 2 TVA had completed Phase I during the week ending 4/4/81. Work is continuing on modification and clearing of the nonconformances discovered during the Phase I inspection.
7.
Safety Related Structures & Supports - Review of Quality Records The inspectors reviewed quality records for the fabrication, installation and inspection of supports on the Residual Heat Removal (RHR) Heat
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Exchanger. The applicable code for safety related structures and supports
is the Structural Welding Code AWS 01.1, as implemented by the Licensee's General Construction Specification G-29-C.
Quality records in the following areas were verified complete and in compliance with the applicable code:
(a) Material (1) Material test reports / certification records (2) Receiving inspection reports (3) Nonconformance reports
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(b)
Installation (1) Construction / erection specification
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(2) Ccmponent installation and location (3) Adherence to testing requirem9nts (c) Insoection (QC) Records (1) Records of inspection activities were complete, legible and readily retrievable.
(2) Qualification records of inspection personnel Within the areas inspected no violations or deviations were observed.
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8.
Safety Related Pipe Supports and Restraint Systems The inspectors reviewed implementing procedures, audits, work procedures, work packages, drawings and completed records of safety related pipe sup-ports and restraints to determine whether they were in compliance with code requirements, as implemen;ed by the licensee's General Construction Speci-fication G-29-C. The following areas were examined:
a.
Review of QA implementing procedures Procedure No.
Title QAAD 18.0 Audits QASP 7.1 Audits of Construction Activities SNP 30.0 Receipt Inspection The first two procedures listed above were reviewed to ascertain that adequate QA audit procedures had been established for this activity and that these procedures included frequency of audits, audit criteria and reporting requirements. In addition SNP-30.0 was reviewed to determine whether means were established to verify that technical requirements, including material and component specifications, acceptance criteria and required documentation were specified in procurement documents.
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b.
Review of Work Packages The following work packages were reviewed:
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l Work Package No's (1) F251 M062-008
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(2) F234 M063-007 (3) F234 M063-035
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(4) F234 M063-003 (5) F300 M068-023 For the above work packages, the inspectors reviewed drawings, work procedures, receiving reports and QC records to determine whether adequate inspection procedures had been established to assure that
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quality requirements had been met.
c.
Review of Work Procedures The following procedures were reviewed to ascertain whether procedures and instruction had been approved by authorized licensee personnel.
(1) SNP Construction Procedure No. P-10
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(2) SNP Construction Procedure No. P-22 l
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(3) SNP Construction Procedure No. P-5 (4) SNP Inspection Instruction No. 30 d.
Review of Records Records for the following dynamic pipe support or restraint systems and fixed pipe support systems were reviewed:
(1) Dynamic pipe Suocorts or Restraints Pipe Hanger ID No.
Type Restraint (a) 2063HPABIH404 Spring Hanger (b) 2063HPABSIH431 Snubber (c) 2063HPABSIH442 Spring
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(d) 2063HPABSIH448 Spring (e) 2063HPABSIH457 Spring (f) 2063HPABSIH465 Spring (g) 2063HPABSIH487 Spring (1) 2063HPASSIH497 Snubber (j) 2063HPR2SI-513-IV Snubber (k) 2063HPR2SIH-023 Snubber (2) Fixed Pipe Supports
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Pipe Hanger ID No.
(a) 2063HPR2SIH-001 (b) 2063HPR2SIH-002 (c) 2063HPR2SIH-004 (d) 2063HPR2SIH-007 (e) 2063HPR2SIH-008 (f) 2063HPR2SIH-010 (g) 2063HPR2SIH-014 (h) 2063HPR2SIH-016 (1) 2063HPR2SIH-018 (j) 2063HPR2SIH-019 Records for the above pipe supports were reviewed to ascertain the following:
(1) Type and classification of pipe support or restraint system comply with appropriate drawings and/or specifications.
(2) Location and spacing meet licensee's specifications and have been verified by QA/QC.
(3) The records confi rm that the specifications and installation procedures were met.
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(4) The required scope of QA/QC inspections were met.
(5) Weld identification / location corresponds to respective weld card, drawing, work order of other welding documentation.
(6) Weldag material used corresponds to the material specified in the licensee's procedures.
(7) Welders were qualified for the welding procedure used.
(8) The examination records were complete and meet the NDE procedure requirements, including personnel qualifications.
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Within the areas inspected no violations or deviations were observed.
9.
Preservice Inspection - Data Review and Evaluation The inspectors reviewed the NOE data packages for the welds listed below, to
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determine whether they met the ASME Code,1974 edition with Summer 1975 Addenda requirements.
Weld No's Report No'1 Size
SGW-A-3 2049, 2072, 2070 & 2073 36" Dia.
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WP-2 2076, 2080, 2136 & 2063 24" Dia.
RCW-15 2050, 2124, 2130 & 2152 6" Dia.
WO203 14, 15, 3" 4 31 0* to 360*
WO506 36, 37, & & 43 0* to 360*
N-2 (inlet nozzle)
46, 59, 58, 86 & 87 0' to 360'
SIS-7-LS 628 & 641 8" Dia.
SIF-206A 1883 & 1888 21s" Dia.
RC-751 1702 & 1821 31" Dia.
RC-2 1718 29" Dia.
For the above welds the inspectors ascertained whather the selected records contained or orovided reference to the following documents and if the documentatin complied with applicable code requirements.
a.
Examination results and data sheets b.
Examinat'.on equipment data
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Calibration data sheets d.
Examination data sheets e.
Records on extent of examination f.
Records on deviation from program and precedures including justi-fication for deviation g.
Records on disposition of findings h.
Reexamination data after repair l
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Identification of NDE material such as penctrant, penetrant cleaner, couplant, films, types, etc.
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Personnel qualification records Within the areas inspected no violations or deviations were pbserved.
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Inspector Followup Items a.
(Closed) Inspector Followup Item (IFI), 328/80-29-06, Cantainment Spray Header left full of water.
Discussions with cognizant licensee per-sonnel disclosed the water in question was demineralized. The header was drained followed by an air test to check operability of all nozzles. The licensee stated and the inspectors agreed that the above conditions posed no throat to the integrity of the stainless steel material.
b.
(Closed) Inspector Followup Item 328/80-22-02, Inadequate visual inspection record card.
The inspectors reviewed changes that the licensee had made to the visual inspection record cards and considers that all applicable coda requirements are adequately addressed,
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(0 pen) Inspector Followup Item 328/81-03-05, Amount of base metal to be penetrant examined is not specified in the penetrant procedure. The licensee had agreed to revise their penetrant procedure to include the
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ASME Code requirements found in Section XI Table IWB-2500. However, this revision had not been implemented at this time.
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